NSUF - Nuclear Science User Facilities

Douglas Porter

Profile Information
Name
Douglas Porter
Institution
Idaho National Laboratory
Expertise
304 Stainless Steel, Fission, Fuel Elements, Hex Block, Irradiated Stainless Steel
Publications:
"Measurement of Helium Generation in AISI 304 Reflector and Blanket Assemblies after Long-Term Irradiation in EBR-II" Frank Garner, B. M. Oliver, L. R. Greenwood, Douglas Porter, Todd Allen, Journal of ASTM International,Research Vol. 20 2013 Link
"Microstructural characterization of high burn-up mixed oxide fast reactor fuel" Brian Gorman, Steven Hayes, Jeffrey King, Douglas Porter, Melissa Teague, Journal of Nuclear Materials Vol. 441 2013 267-273 Link
High burn-up mixed oxide fuel with local burn-ups of 3.4–23.7% FIMA (fissions per initial metal atom) were destructively examined as part of a research project to understand the performance of oxide fuel at extreme burn-ups. Optical metallography of fuel cross-sections measured the fuel-to-cladding gap, clad thickness, and central void evolution in the samples. The fuel-to-cladding gap closed significantly in samples with burn-ups below 7–9% FIMA. Samples with burn-ups in excess of 7–9% FIMA had a reopening of the fuel-to-cladding gap and evidence of joint oxide-gain (JOG) formation. Signs of axial fuel migration to the top of the fuel column were observed in the fuel pin with a peak burn-up of 23.7% FIMA. Additionally, high burn-up structure (HBS) was observed in the two highest burn-up samples (23.7% and 21.3% FIMA). The HBS layers were found to be 3–5 times thicker than the layers found in typical LWR fuel. The results of the study indicate that formation of JOG and or HBS prevents any significant fuel-cladding mechanical interaction from occurring, thereby extending the potential life of the fuel elements.
"Microstructure and mechanical behavior of neutron irradiated ultrafine grained ferritic steel" Ahmad Alsabbagh, Apu Sarkar, Brandon Miller, Jatuporn Burns, Leah Squires, Douglas Porter, James Cole, Korukonda Murty, Materials Science and Engineering A Vol. 615 2014 128-138 Link
Neutron irradiation effects on ultra-fine grain (UFG) low carbon steel prepared by equal channel angular pressing (ECAP) have been examined. Counterpart samples with conventional grain (CG) sizes have been irradiated alongside with the UFG ones for comparison. Samples were irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) to 1.37 dpa. Atom probe tomography revealed manganese and silicon-enriched clusters in both UFG and CG steel after neutron irradiation. Mechanical properties were characterized using microhardness and tensile tests, and irradiation of UFG carbon steel revealed minute radiation effects in contrast to the distinct radiation hardening and reduction of ductility in its CG counterpart. After irradiation, micro hardness indicated increases of around 9% for UFG versus 62% for CG steel. Similarly, tensile strength revealed increases of 8% and 94% respectively for UFG and CG steels while corresponding decreases in ductility were 56% versus 82%. X-ray quantitative analysis showed that dislocation density in CG increased after irradiation while no significant change was observed in UFG steel, revealing better radiation tolerance. Quantitative correlations between experimental results and modeling were demonstrated based on irradiation induced precipitate strengthening and dislocation forest hardening mechanisms.
Presentations:
"Measurement of depth-dependent swelling in thick non-uniform irradiated 304 stainless steel blocks using nondestructive ultrasonic techniques" Frank Garner, Paula Freyer, T. Okita, Y. Isobe, J. Etoh, M. Sagisaka, T. Matsunaga, Yina Huang, J.M.K. Wiezorek, Douglas Porter, Fontevraud 8 - Contributions of Materials Investigations and Operating Experience to LWR's Safety, Performance and Reliability September 3-6, (2014) Link
"Measurement of void swelling in thick non-uniformly irradiated 304 stainless steel blocks using nondestructive ultrasonic techniques " Frank Garner, Paula Freyer, Huang Hanchen, Douglas Porter, Proceedings of Fontevraud 8 - Contributions of Materials Investigations and Operating Experience to LWR's Safety, Performance and Reliability August 16-16, (2014)
"Void swelling and resultant strains in thick 304 stainless steel components in response to spatial gradients in neutron flux-spectra and irradiation temperature" Frank Garner, Paula Freyer, Douglas Porter, Yina Huang, Proceedings of 16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors [unknown] Link
"Void Swelling of Annealed 304 Stainless Steel at ~370-385C and PWR-Relevant Displacement Rates" G.M> Bond, Bulent Sencer, Frank Garner, M.L. Hamilton, Todd Allen, Douglas Porter, 9th International Conference on Environmental Degradation of Materials in Nuclear Power Systems ? Water Reactors [unknown] Link
"Void Swelling of Annealed 304 Stainless Steel at ~370-385C and PWR-Relevant Displacement Rates" G.M. Bond, Francis Garner, Todd Allen, Douglas Porter, 9th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors August 1-2, (1999)

About Us

The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.

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